ML20024A386

Forwards Addl Info to Justify 820701 10CFR50.48 & App R Schedule Exemption Requests Discussed at 830330 Meeting. Plan Being Developed to Complete Maint & Design Changes. W/Two Oversize Drawings.Aperture Cards Available in PDR

ML20024A386
Person / Time
Site:	Hatch
Issue date:	06/14/1983
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20024A387	List: ML20024A386
References
RTR-NUREG-0661, RTR-NUREG-0737, RTR-NUREG-661, RTR-NUREG-737 IEB-79-01B, IEB-79-1B, NED-83-349, TAC-43754, TAC-43755, TAC-47143, TAC-48071, TAC-48072, TAC-48748, TAC-48749, NUDOCS 8306170202
Download: ML20024A386 (4)

Text

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.e Georgia Power Corrpany 333 Piedmont Avenue AUanta. Georg a 30308 Te!ephone 404 526-6526 Matric Address:

Post otSce Box 4545 Acanta, Georg a 30302 Georgia Power L. T. Gucw a tre southern ettcr:c sa:em Chief Nuclear Eng neer Power Generation Departrrent NED-83-349 June 14, 1983 Director of foclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 ADDITIONAL INFORMATION ON 10 CFR 50.48 Ato APPENDIX R MODIFICATION SOiEDULE Gentlemen:

The draft Safety Evaluation Report (SER) transmitted by your letter dated January 20, 1983, indicated that the July 1, 1982, 10 CFR 50.48 senedule exemption request did not provide sufficient basis to justify granting the schedule exemptions. A meeting with the PRC Staff was held on March 30, 1983, to discuss the denied exemptions and other aspects of the Appendix R compliance program at Georgia Power Company (GPC).

The Staff requested that additional information to justify the schedule exemption be supplied.

This letter contains additional information to justify the exemption.

In order to properly allocate manpower and resources to accomplish the various work items related to maintenance and design changes at Plant Hatch, GPC is developing a five-year plan.

The plan will cover known Design Change Requests (DCRs), licensing commitments, major maintenance items, and known outagc requirements. The following is a listing of the number of DCRs planned to ba worked each year for each unit:

1983 Non-Outage:

Unit 1:

39 Unit 2:

27 s

1984 Outage:

Unit 1:

65 Unit 2:

53 1984 Non-Outage:

Unit 1:

30 Unit 2:

20 1985 Outage:

Unit 1:

21 Unit 2:

18 1985 Non-Outage lhit 1:

9 Unit 2:

6 These DCRs are for plant modifications related to licensing commitments such as equipment qualification in accordance with IEB 79-01B, NUREG-0737, TMI-related requirements, NUREG-0661, Mark I

torus mcdifications and NUREG-0737 Supplement 1 Emergency Response Facilities, as well as, general plant reliability and operability maintenance requirements.

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GeorgiaPower A Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 June 14, 1983 Page 2 The number of manhours associated with plant modifications is significant.

Two of the largest plant modifications presently scheduled are related to Equipment Qualification and NUREG-0737.

The equipment qualification modifications are related to I & E Bulletin 79-01B and are scheduled to be completed by 1984.

A major project is the installation of an Analog Transmitter Trip System.

This modification involves replacement of over 170 instruments per unit.

The present manhour estimate is 70,000 manhours for installation and 30,000 manhours for supporting engineering design per unit.

The remaining portion of the equipment qualification modifications involve replacement of various motors and actuators for valves, solenoids, pressure switches, and valves which could possibly double the manhour estimates.

The major NUREG-0737 TMI-related modification is the installation of a Safety Parameter Display System.

This system is required by the NRC and is expected to be installed by 1985.

The present scheduling estimate calls for approximately 102,000 manhours to install over 200,000 feet of cable and related equipment.

While these two modifications are extensive, they represent only part of the planned modifications at Plant Hatch.

Due to this large amount of work remaining on prior licensing commitments and probable high priority future safety-related work, we feel that the schedule of Appendix R modifications to be completed by the third refueling outage following approval of the modifications to be a realistic schedule.

The previous listing of planned DCRs does not include the modification necessary for Appendix R.

Following the March 30, 1983 meeting with the NRC staff, the types of design modifications that the staff would accept were clarified so that the detailed planning and design effort to accomplish the Appendix R modifications could begin.

These modifications involve rerouting of required circuits, cable wrapping with a one-hour fire rated material, installation of additional sprinkler systems and installation of additional fire detector systems.

A tentative schedule for the installation of the Appendix R modifications is attached solely for information purposes to show the sequencing of the various activities.

While the particular sequencing of the various activities may change, the overall completion date for modifications is expected to be September 1986.

The attached schedule is based upon using at least two people from each engineering discipline on each design activity and a minimum of two people for each installation activity.

The installation of cable wrapping is scheduled after completing all other work.in an area to prevent damage to the wrap. As uns

Georgia Power A Director of M! clear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 June 14, 1983 Page 3 shown on the schedule, the Unit 1 and 2 sprinkler systems are tentatively scheduled for completion as follows:

Control Building 130' elevation in November 1984, Reactor Building 158' elevation in February 1985, Reactor Building 87' elevation (Torus Area) in June 1985, Reactor Building 130' elevation in October 1985, and Reactor Building 185' elevation in December 1985.

The Unit 1 and 2 smoke detection and multiplex system is tenatively scheduled as follows:

LPCI Inverter Room in May 1984, Reactor Building 158' elevation in March 1985, Control Building 130' elevation in April 1985, and Reactor Building 87' elevation in June 1985.

The final functional test of the multiplex system is tentatively scheduled for July 1985. The major circuit rerouting is. expected to be completed for Unit 1 in March 1985.

The thit 2 circuit rerouting for the Control Building 130' elevation and Annunciator Room is expected to be completed in June 1984.

The Unit 2 Reactor Building 130' elevation cable rerouting is expected to be completed in September 1985.

The protection of miscellaneous electrical equipment from the effects of water spray is scheduled to be completed in September 1985.

The protection of miscellaneous electrical equipment from the effects of water spray is expected to be completed in September 1984 for Unit 1 and November 1984 for Unit 2.

The Unit 1 and 2 RPS room door is scheduled to be installed in August 1984.

The fire door for panel R25-S002 on Unit 1 is scheduled to be installed in March 1984.

The cable wrap installation is tentatively scheduled as follows:

Riverwater Intake Structure in March 1984, Unit 1 and 2 East Cableway in April 1985, Unit 1 Control Building 112' elevation in February 1986, 4160/600V transformer room in February 1986, Unit 1 and 2 Control Building 130' elevation in February 1986, Unit 1 Reactor Building 158' elevation in March 1986, RPS room in March 1986, Unit 1 600V switchgear room in March 1986, Unit 2 Diesel Generator Building in March 1986, Unit 1 Annunciator Room in April 1986, Unit 1 and 2 Reactor Building 87' elevation in July 1986, and Unit 1 and 2 Reactor Building 130' elevation in August 1986.

700775

Georgialbwer d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 June 14, 1983 Page 4 The high/ low pressure interface modifications will be installed in conjunction with the Appendix. R modifications and are scheduled to be completed in June 1986.

As ' stated in the July ~ 1,1982 submittal, the previous Safety Evaluation for Hatch Nuclear Plant. concluded that the plant exhibits a high degree of fire protection safety at this time.

Therefore, the exemption from the schedule requirements of 10 CFR 50.48 is justified on the basis that compliance would not enhance fire protection safety, and a delay will not endanger the public health and safety.

If' you _ should have an' ~ questions concerning this information, please y

contact this office.

.Yours-trul wb o/,

L. T. Gucwa WEB /clh Enclosure xc:

J. T..Beckham, Jr.

H.'C.' Nix, Jr.

J. P. O'Reilly (!fC Region-II)

Senior Resident Inspector 4

I 700775 -

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